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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
J. P. Moore, R. S. Graves, D. L. McElroy
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 88-93
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16277
Articles are hosted by Taylor and Francis Online.
The thermal conductivity λ, electrical resistivity ρ, and absolute Seebeck coefficient S of two grades of nearly isotropic graphite were measured from 300 to 1000°K both before and after neutron irradiation up to 5.0 × 1021 n/cm2 (>50 keV). Nominal irradiation temperatures were 823, 923, and 1023°K. The thermal resistance, λ−1, of the unirradiated graphites was proportional to T from 500 to 1000°K. Neutron irradiation decreased λ at 300°K by a factor of 4.5 and increased ρ at 300°K by 2.5, in general agreement with previous investigations, and irradiation changed S from small negative values to large positive ones. The product of thermal conductivity and electrical resistivity was nearly constant with fluence from 2.6 × 1021 to 5.0 × 1021 n/cm2.